ML070810417
| ML070810417 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/19/2007 |
| From: | Richard Ennis NRC/NRR/ADRO/DORL/LPLI-2 |
| To: | |
| Ennis R, NRR/DORL, 415-1420 | |
| Shared Package | |
| ml070811052 | List: |
| References | |
| TAC MD2786, TAC MD2787 | |
| Download: ML070810417 (5) | |
Text
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4 -
(2)
Technical Specifications and Environmental Plan
- The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
260, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Special Low Power Test Program PSE&G shall complete the training portion of the Special Low Power Test Program in accordance with PSE&G's letter dated September 5, 1980 and in accordance with the Commission's Safety Evaluation Report "Special Low Power Test Program",
dated August 22, 1980 (See Amendment No.
2 to DPR-75 for the Salem Nuclear Generating Station, Unit No.
- 2) prior to operating the facility at a power level above five percent.
Within 31 days following completion of the power ascension testing program outlined in Chapter 13 of the Final Safety Analysis Report, PSE&G shall perform a boron mixing and cooldown test using decay heat and Natural Circulation.
PSE&G shall submit the test procedure to the NRC for review and approval prior to performance of the test.
The results of this test shall be submitted to the NRC prior to starting up following the first refueling outage.
(4)
Initial Test Program PSE&G shall conduct the post-fuel-loading initial test program (set forth in Chapter 13 of the Final Safety Analysis Report, as amended) without making any major modifications of this program unless modifications have been identified and have received prior NRC approval.
Major modifications are defined as:
(a)
Elimination of any test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential; (b)
Modification of test objectives, methods or acceptance criteria for any test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential; (c)
Performance of any test at a power level different by more than five percent of rated power from there described; and Amendment No. 2 6 0
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.5 PAGE EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 3/4.5.2 3/4.5.3 3/4. 5.4 3/4. 5.5 3/4.6 3/4.6.1 ACCUMULATORS 3/4 5-1 ECCS SUBSYSTEMS -
Tavg Ž 350
.F 3/4 5-3 ECCS SUBSYSTEMS -
Tavg < 350OF..........................
3/4 5-7 SEAL INJECTION FLOW..................................
3/4 5-8a REFUELING WATER STORAGE TANK.........................
3/4 5-9 CONTAINMENT SYSTEMS PRIMARY CONTAINMENT Containment Integrity..............
Containment Leakage................
Containment Air Locks..............
Internal Pressure..................
Air Temperature....................
Containment Structural Integrity....
DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System...........
Spray Additive System..............
Containment Cooling System.........
.3/4
.3/4
.3/4
.3/4
.3/4
.3/4 6-1 6-2 6-4 6-6 6-7 6-8 3/4.6.2
.3/
.3/
.3/
4 4
4 6-10 6-11 6-12 3/4.6.3 3/4.6.4 CONTAINMENT ISOLATION VALVES.........................
3/4 6-14 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers...................................
3/4 6-21 Electric Hydrogen Recombiners 3/4 6-22 SALEM 7 UNIT 2 VI Amendment No. 260
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Note that the elements of TS 3.6.1.7 and 4.6.1.7 were relocated to TS 3/4.6.3.
SALEM -
UNIT 2 3/4 6-9 Amendment No.
260
CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 Each containment isolation valve shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
NOTE 1 Penetration flow paths, except for the containment purge valves, may be unisolated intermittently under administrative controls.
Note 2 A containment purge valve is not a required containment isolation valve when its flow path is isolated with a testable blind flange tested in accordance with SR 4.6.1.2.b. The required containment purge supply and exhaust isolation valves shall be closed.
(Valves immobilized in shut position with control air to valve operators isolated and tagged out of service).
NOTE 3 The containment pressure-vacuum relief isolation valves may be opened on an intermittent basis, under administrative control, as necessary to satisfy the requirement of Specification 3.6.1.4.
- 1. With one or more of the containment isolation valve(s) inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either:
- a.
Restore. the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or
- b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or
- c.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or
- d.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- 2.
With one required containment purge supply and/or exhaust isolation valve open, close the open valve(s) within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.3.1 DELETED SALEM -
UNIT 2 3/4 6-14 Amendment No.260
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each containment isolation valve shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
- a.
Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.
- b.
Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.
- c.
NOT USED
- d.
Verifying that on a Containment Purge and Pressure-Vacuum Relief isolation test signal, each'required Purge and each Pressure-Vacuum Relief valve actuates to its isolation position.
- e.
Verifying that the Containment Pressure-Vacuum Relief Isolation valves are limited to
- 600 opening angle.
4.6.3.3 At least once per 18 months, verify that on a main steam isolation test signal, each main steam isolation valve actuates to its isolation position.
4.6.3.4 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
'4.6.3.5 Each required containment purge isolation valve shall be demonstrated OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each closing of the valve, except when the valve is being used for multiple cyclings, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying that when the measured leakage rate is added to the leakage rates determined pursuant to Specification 4.6.1.2.b for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60La.
4.6.3.6 A pressure drop test to identify excessive degradation of resilient valve seals shall be conducted on the:
a.'
Required Containment Purge Supply and Exhaust Isolation Valves at least once per 6 months.
b, Deleted.
4.6.3.7 The required containment purge supply and exhaust isolation valves shall be determined closed at least once per 31 days.
SALEM -
UNIT 2 3/4 6-15 Amendment No.260